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Volume 159

Number 1 | Number 2 | Number 3

Number 1

A Hybrid Transport-Diffusion Algorithm for Monte Carlo Radiation-Transport Simulations on Adaptive-Refinement Meshes in XY Geometry

Jeffery D. Densmore, Thomas M. Evans, Michael W. Buksas

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 1-22

Technical Paper

Shielding Calculations for a Spent Fuel Storage Cask: A Comparison of Discrete Ordinates, Monte Carlo, and Hybrid Methods

R. J. Sheu, A. Y. Chen, Y.-W. H. Liu, S. H. Jiang

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 23-36

Technical Paper

Efficient Generation of One-Group Cross Sections for Coupled Monte Carlo Depletion Calculations

E. Fridman, E. Shwageraus, A. Galperin

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 37-47

Technical Paper

Use of Local Variation Method for Nuclear Design Calculations

A. I. Zhukov

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 48-55

Technical Paper

New 237Np Burning Strategy in a Supercritical CO2-Cooled Fast Reactor Core Attaining Zero Burnup Reactivity Loss

Hoai Nam Tran, Yasuyoshi Kato

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 83-93

Technical Paper

Subthreshold Fission Cross Section of 237Np

F. Tovesson, T. S. Hill

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 94-101

Technical Paper / dx.doi.org/10.13182/NSE07-55

Spallation Product Distributions and Neutron Multiplicities for Accelerator-Driven System Using the CRISP Code

S. Anéfalos Pereira, A. Deppman, G. Silva, J. R. Maiorino, A. dos Santos, S. B. Duarte, O. A. P. Tavares, F. Garcia

Nuclear Science and Engineering / Volume 159 / Number 1 / May 2008 / Pages 102-105

Technical Note

Number 2

A Functional Monte Carlo Method for k-Eigenvalue Problems

Edward W. Larsen, Jinan Yang

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 107-126

Technical Paper

Linear and Quadratic Hexahedral Wavelets on the Sphere for Angular Discretizations of the Boltzmann Transport Equation

A. G. Buchan, C. C. Pain, M. D. Eaton, A. J. H. Goddard, R. P. Smedley-Stevenson

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 127-152

Technical Paper

Benchmark Calculation of WIMS/RFSP Against Physics Measurement Data of Wolsong Nuclear Power Plants

Hangbok Choi, Chang Je Park

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 153-168

Technical Paper

A Neutron Transport Benchmark in One-Dimensional Cylindrical Geometry: Revisited

B. D. Ganapol

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 169-181

Technical Paper

Measurements of Thermal Neutron Diffraction and Inelastic Scattering in Reactor-Grade Graphite

C. D. Bowman, D. C. Bowman, T. Hill, J. Long, A. P. Tonchev, W. Tornow, F. Trouw, Sven Vogel, R. L. Walter, S. Wender, V. Yuan

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 182-198

Technical Paper

Measurement of Neutron Capture Resonance Integrals on Bromine Isotopes

E. L. Dorval, M. A. Arribére, S. Ribeiro Guevara

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 199-212

Technical Paper

Modeling of High-Precision Neutron Nonelastic Cross Sections

F. S. Dietrich, J. D. Anderson, R. W. Bauer, S. M. Grimes, D. P. McNabb

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 213-220

Technical Paper

Identification of Optimal Number of Histogram Bars for Large Data Trends

Plamen V. Petkov

Nuclear Science and Engineering / Volume 159 / Number 2 / June 2008 / Pages 221-227

Technical Note

Number 3

Analytic Function Expansion Nodal Method for Multigroup Diffusion Equations in Cylindrical (r,,z) Geometry

Nam Zin Cho, Jaejun Lee

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 229-241

Technical Paper

Finite Element Transport Using Wachspress Rational Basis Functions on Quadrilaterals in Diffusive Regions

Gregory G. Davidson, Todd S. Palmer

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 242-255

Technical Paper

Efficient Subspace Methods-Based Algorithms for Performing Sensitivity, Uncertainty, and Adaptive Simulation of Large-Scale Computational Models

Hany S. Abdel-Khalik, Paul J. Turinsky, Matthew A. Jessee

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 256-272

Technical Paper

A New Approach to Estimate Importance for Weight Window in Forward Monte Carlo Calculations

Isao Murata, Detlef Filges, Frank Goldenbaum

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 273-283

Technical Paper

Research of Point Flux Estimation Method

Chunyan Li, Junli Li, Jianping Cheng, Zhen Wu, Lucheng Pei, Jiajin Fan

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 284-295

Technical Paper

Purely Angular Effects of Photon Buildup Factors for Thin Shields of Lead, Iron, Aluminum, and Water

H. Omar Wooten, Donald J. Dudziak, Nolan E. Hertel, Drew E. Kornreich, Adam C. Davis

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 296-310

Technical Paper / dx.doi.org/10.13182/NSE06-42

The Measurement of the Coolant Pressure Fluctuation and the Mechanical Vibration of the Equipment, and the Analysis of the Vibrodynamic Processes in a Nuclear Power Plant with a VVER-1000

M. Gholampour, K. N. Proskouriakov

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 311-320

Technical Paper

Tritium-Charged Capacitor

A. Kavetsky, G. Yakubova, M. Sychov, Q. Lin, G. Walter, D. Chan, S. Yousaf, H. Socarras, J. Abrefah, K. Bower

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 321-329

Technical Paper

A Quasi-Linear Implementation of High-Resolution Time Integration for the Pn Equations

Ryan G. McClarren, James Paul Holloway

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 330-337

Technical Note

Two Media Method: An Alternative Methodology for the Measurement of Attenuation Coefficients of Irregularly Shaped Samples

Sukhpal Singh, Gurmel S. Mudahar, Ashok Kumar, Kulwant Singh Thind

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 338-345

Technical Note

A Fission Chamber Measurement of the natB(d,n) Cross Section for Use in Neutron Detector Calibration

A. R. Di Lullo, T. N. Massey, S. M. Grimes, D. E. Carter, J. E. O'Donnell, D. Jacobs

Nuclear Science and Engineering / Volume 159 / Number 3 / July 2008 / Pages 346-350

Technical Note

 
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